edge impurity transport study in stochastic layer of lhd and scrape-off layer of hl-2a
DESCRIPTION
Edge impurity transport study in stochastic layer of LHD and scrape-off layer of HL-2A. M. Kobayashi, S. Morita, C.F. Dong, Y. Feng*, S. Masuzaki, M. Goto, T. Morisaki, H.Y. Zhou, H. Yamada and the LHD experimental group National Institute for Fusion Science, Toki 509-5292, Japan - PowerPoint PPT PresentationTRANSCRIPT
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
Edge impurity transport study in stochastic layer of LHDand scrape-off layer of HL-2A
1
M. Kobayashi, S. Morita, C.F. Dong, Y. Feng*, S. Masuzaki, M. Goto, T. Morisaki, H.Y. Zhou, H. Yamada and the LHD experimental group
National Institute for Fusion Science, Toki 509-5292, Japan*Max-Planck-Institute fuer Plasmaphysik, D-17491 Greifswald, Germany
Z.Y. Cui, Y.D. Pan, Y.D. Gao, J. Cheng, P. Sun, Q.W. Yang and X.R. DuanSouthwestern Institute of Physics, P. O. Box 432, Chengdu 610041, China
1. Introduction
2. Edge impurity transport and energy transport
3. Modelling results of LHD & HL-2A
Effects of magnetic field geometry
4. Summary
Contents
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
Introduction : Impurity transport in SOL/DivertorUnderstanding of impurity transport in SOL/Divertor region is important for control ofImpurity influx to core, Radiation distribution & intensity in SOL, Material migration.
2
Effects of the different magnetic field geometry on the edge
impurity transport?
Divertor optimization for fusion reactor is ongoing in tokamaks (2D), stellarators, non-axisymmetric tokamaks (3D).
e.g. Ergodic divertor in TEXT, Tore Supra, TEXTOR-DED,DIII-D etc.
Stochastic field as a tool for controlling edge plasma
3D divertor configuration intrinsic edge stochastization
Helical devices with non-axisymmetric configurationITER: Tokamak
2D axi-symmetric SOL(Closed, V-shaped divertor)
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
//-Impurity transport model ↔ Ion energy transport
Momentum : // - Classical force balance
Friction
....1
71.06.2 //22//////
s
nT
nZeE
s
TZ
s
TZ
VVm
t
Vm zi
z
ei
s
ziz
zz
Ion thermal force Electric field
Impurity pressure gradient force
score SOL
LCFS
targ
et
Ti
dTi/ds
ViII
Recycling
Thermal
Friction
3
Electron thermal force
s
T
m
ZVV i
z
si
impZ
2////
6.2
In a steady state
iD
iV
ii
i
iii
i
z
s
i
q
q
s
TT
VTn
s
T
m
Z
V
//
//
5.20
//
2// 2
5
6.2
The force balance is closely related to ion energy transport.
Extra function is added to energy transport module of EMC3-EIRENE to analyze the energy transport.
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
4
• Dz is same as the value of bulk plasma (which is deduced from experiments).• Dz has No charge dependence. No drift.
Mass : ⊥- Diffusion with anomalous coefficient
zzzzzzzzzzzz
zzzz
nRnRnSnS
nbbDbVn
111111
//
Ionization, recombination
Diffusion
Source at PFC :• Divertor plate or first wall with 0.05 eV ejection energy.
Simplification for perpendicular transport model
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
5
3D modelling of LHD edge region (EMC3-EIRENE)
Boundary conditionsBohm condition at divertor platesPower entering the SOLDensity on LCMSSputtering coefficient
SOLPSOL
Core plasma
LCMS
wall
targ
et
EMC3
Div
erto
rle
gs
C0
H,H2
Computational mesh, configuration and installations Core, CX-neutral transport, particle source SOL, EMC3 simulation domainVacuum of plasma*
Cross-field transport coefficients e=i=3D roughly holdsspatially constant (global transport) determined experimentally
Example of LHD helical divertor
Physics modelStandard fluid equations of mass, momentum, ion and electron energyTrace impurity fluid model (Carbon)Kinetic model for neutral gas (Eirene)
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
-2
-1.5
-1
-0.5
0
0.5
1
1.5
2
2 2.5 3 3.5 4 4.5 5 5.5 6
vessel_162
C
B
6
divertor plate
Helical coils
R=3.90 ma~0.70 m
LHD
HL-2A
LHD heliotron and HL-2A tokamak : distinct magnetic flux tube topology
R=1.65 ma= 0.40 m
105 104 103 102 101 100
Connection length (m)
1 m
1 m
Stochastic layerLC=10 m~1km
Scrape-off layer
LC~40 m
Divertor plate
Divertor plate
Divertor legs
Separatrix
R
Z
Enhanced interaction ⊥between flux tubes
Dominant // transportdivertor entrance
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
7
10-1
100
101
100
101
102
103
0 10 20 30
PARA_DATA_NUP050_50+-05m_out
nz/nzd Spz(A/m**3)
s (m)
(c) nimp / nimp_down
Sp imp (A/m3)
-1 105
0
1 105
0 10 20 30
PARA_DATA_NUP050_C1_50+-05m_out
Ther_e(m/s)Ther_iFricE//Vimp
s (m)
//V
(105
m/s
)
0
4
-4
theV//thi
V//
fricV//E
V//
imp
ZV
//(b)
(MW
/m2)
//q
=0.3x1019 m-3LCFSn
e
Dq//i
Dq//
i
Vq//
e
Vq//
-2
-1
0
0 10 20 30
PARA_DATA_NUP050_50+-05m_out
COND_e(MW/m**2)COND_iCONV_eCONV_i
s (m)
(a)
Divertor plate X-point
-1
-0.5
0
0.5
1 1.5 2
trace_outers 17:42:11 2011/03/26
C
Z
C
ZZ (m
)
R (m)
0 m
510
15
202530
35
40
45
50 m
R
Z
Divertor plates
Low density (collisionality) case : HL-2AStrong thermal force ( )
Impurity buildup at upstream
iV
iD qq ////
Coordinate s
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
8
-3
-2
-1
0
0 10 20 30
PARA_DATA_NUP120_C1_50+-05m_out
COND_e(MW/m**2)COND_iCONV_eCONV_i
s (m)
=0.6x1019 m-3LCFSn
(MW
/m2)
//q
(d)
-2 104
-1 104
0
1 104
2 104
0 10 20 30
PARA_DATA_NUP120_C1_50+-05m_out
Ther_e(m/s)Ther_iFricE//Vimp
s (m)
//V
(104
m/s
)
0
2
-2
(e)
10-2
10-1
100
100
101
102
103
0 10 20 30
PARA_DATA_NUP120_C1_50+-05m_out
nz/nzd Spz(A/m**3)
s (m)
Sp imp (A/m3)
nimp / nimp_down
(f)
-1
-0.5
0
0.5
1 1.5 2
trace_outers 17:42:11 2011/03/26
C
Z
C
ZZ (m
)
R (m)
0 m
510
15
202530
35
40
45
50 m
R
Z
Divertor plates
High density (collisionality) case : HL-2A Strong friction force near divertor ( )
Impurity screening (against divertor source) Residual thermal force at upstream ( )
iV
iD qq ////
iV
iD qq ////
e
Dq//i
Dq//
i
Vq//
e
Vq//
theV//thi
V//
fricV//E
V//
imp
ZV
//
Divertor plate
Coordinate s
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
999
Magnetic field structure in LHD (Large Helical Device)LHD
Helical coilsConnection length (LC) distribution in poloidal cross section
3.9 m
radial
poloidal10/8
10/710/6
10/2
10/3
10/4
10/5
Mode structure n/m
Edge surface layers*
Stochastic region*
reff (m)
0.70
0.65
0.60
Divertor
Core plasma
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
10
radial
poloidal
Edge surface layers*
Stochastic region*
reff (m)
0.70
0.65
0.60
Divertor
Core plasma
10-1
100
101
102
1 100 1 101 1 102 1 103 1 104
P08_D0.50_SHI1.50_C1_NUP2.0_DP3DT3dt1e-9_LCSPEC 14:46:29 2011/05/04
e_cond_p_w(MW/m**2)e_conv_p_wi_cond_p_wi_conv_p_w
LC (m)
i=52
reff=0.72 m(M
W/m
2 )//q
10-1
100
101
102
1 100 1 101 1 102 1 103 1 104
P08_D0.50_SHI1.50_C1_NUP2.0_DP3DT3dt1e-9_LCSPEC 14:29:14 2011/05/03
e_cond_p_w(MW/m**2)e_conv_p_wi_cond_p_wi_conv_p_w
LC (m)
i=12
reff=0.65 m
(MW
/m2 )
//q
LC (m)104103102101100
10-1
100
101
102
1 100 1 101 1 102 1 103 1 104
P08_D0.50_SHI1.50_C1_NUP2.0_DP3DT3dt1e-9_LCSPEC 14:28:32 2011/05/03
e_cond_p_w(MW/m**2)e_conv_p_wi_cond_p_wi_conv_p_w
LC (m)
i=12
reff=0.60 m
(MW
/m2 )
//qe
Dq//
i
Dq//
i
Vq//
e
Vq//
Upstream
Downstream
Low density (collisionality) case : LHDStrong thermal force ( )
Impurity buildup at upstream
-10
-5
0
5
10
0.6 0.65 0.7
P08_D0.50_SHI1.50_C1_NUP2.0_DP3DT3_RPRF_PRE
fric(e4m/s)e_thermi_thermE//_Z=3F_BAL
reff (m)
theV//thi
V//
fricV//E
V//
imp
ZV
//
=2.0x1019 m-3LCFSn
//V
(104
m/s
)
(a)
10-1
100
10-4
10-3
10-2
10-1
0.6 0.65 0.7
P08_D0.50_SHI1.50_C1_NUP2.0_DP3DT3_RPRF_PRE
nz/nzd Sp_imp(e22/s/m**3)
reff (m)
nimp/nimp_down
Sp imp
(1022/s/m3)(b)
Radial impurity profile
iV
iD qq ////
DivertorCore plasma
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
10-1
100
101
102
1 100 1 101 1 102 1 103 1 104
P08_D0.50_SHI1.50_C1_NUP5.0_DP3DT3_LCSPEC 14:52:26 2011/05/04
e_cond_p_w(MW/m**2)e_conv_p_wi_cond_p_wi_conv_p_w
LC (m)
i=52
LC (m)104103102101100
reff=0.72 m
11
radial
poloidal
Edge surface layers*
Stochastic region*
reff (m)
0.70
0.65
0.60
e
Dq//
iDq//
i
Vq//
e
Vq//
Upstream
Downstream
10-1
100
101
102
1 100 1 101 1 102 1 103 1 104
P08_D0.50_SHI1.50_C1_NUP5.0_DP3DT3_LCSPEC 14:10:35 2011/05/03
e_cond_p_w(MW/m**2)e_conv_p_wi_cond_p_wi_conv_p_w
LC (m)
i=30
reff=0.65 m
10-1
100
101
102
1 100 1 101 1 102 1 103 1 104
P08_D0.50_SHI1.50_C1_NUP5.0_DP3DT3_LCSPEC 14:09:02 2011/05/03
e_cond_p_w(MW/m**2)e_conv_p_wi_cond_p_wi_conv_p_w
LC (m)
i=12
reff=0.60 m
(MW
/m2 )
//q(M
W/m
2 )//q
(MW
/m2 )
//qHigh density (collisionality) case : LHDStrong friction force @ downstream ( )Impurity screeningSuppression of thermal force at upstream ( )
iV
iD qq ////
iV
iD qq //// ~
-4
-2
0
2
4
0.6 0.65 0.7
P08_D0.50_SHI1.50_C1_NUP5.0_DP3DT3_RPRF_PRE
fric(e4m/s)e_thermi_thermE//_Z=3F_BAL
reff (m)
//V
(104
m/s
)
=5.0x1019 m-3LCFSn
(c)
10-1
100
10-4
10-3
10-2
10-1
0.6 0.65 0.7
P08_D0.50_SHI1.50_C1_NUP5.0_DP3DT3_RPRF_PRE
nz/nzd Sp_imp(e22/s/m**3)
reff (m)
(d)
Radial impurity profile
Divertor
Core plasma
DivertorCore plasma
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
12
0.1
1
10
0.1 1 10
LHD_model_Tu_nu_Td_nd_div_source
LHD div sourceLHD wall sourceHL-2A div sourceHL-2A wall source
nuSOLi*ion
SOL
*
imp
dowm
imp
LCFSn
n/
HL-2A
LHD
Divertor sourceWall source
Scr
eeni
ng
Impurity screening as a function of and impurity source locationion
SOL
*
HL-2A: very strong screening against divertor source, but weak against first wall sourceLHD: modest screening against divertor source, but effective against first wall too
Geometrical effect
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
13
100
101
102
103
10-1 100 101 102
papra-perp_analytical_model 18:11:08 2011/07/13Te,i (eV)Te,i (eV)Te,i (eV)Te,i (eV)TiTiTiTiTiTiTiTiTiTiTiTiTiTin
e (1019 m-3)
ion
10-3
10-2
10-1
HL-2A
LHD
q //=q⊥
for =10-4
(b)
Edge plasma parameter range of LHD and HL-2A(effects of perpendicular transport)
HL-2A: high density and low temperature at downstream because of strong up-down coupling through SOL flux tubes
LHDHL-2A
32 , updownupdown nnnT
Preferable for increasing ratio iD
iV qq //// /
LHD: enhanced perpendicular transport in stochastic layer weakens the up-down coupling
5.11, udud nnnT
Modest change of at downstreamiD
iV qq //// /
qq//
qq ~//
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
14
10-2
10-1
100
101
102
0.6 0.65 0.7
FLUX_1e19_25eV_375_100000pa
Para/Perp_iPara/Perp_iPara/Perp_iPara/Perp_i
reff (m)
25eV
50eV
100eV
200eV
ion
i
D
i
Dq
q
///
(b)
Enhanced perpendicular transport in stochastic layer of LHD can replace withsuppression of thermal force at upstream
iDq//
iDq
Radial profiles of ion energy transport ratio between // and components in LHD⊥
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
15
3 12 0 -1 -2 -3Friction – Thermal force (104 m/s)
Friction force
dominant
Thermal force
dominant
nLCFS=5.0x1019 m-3
LHD
nLCFS=0.59x1019 m-3
HL-2A
Distribution of screening region in LHD and HL-2A
Residual thermal force
Flow acceleration Flow acceleration
No flow acceleration
LHD: Screening region distributed poloidally screening effect is independent of impurity source location
HL-2A: Screening region localized near divertor plate screening effect is very sensitive to impurity source location
Inclusion of large upstream flow observed in experiments might alter the results
6th Japan Korea workshop 28-29 July 2011, NIFS, Toki-city Japan
Summary
Modelling resultsThe modelling shows impurity screening for the both devices.
The screening effect is different between the both devices against collisionality (density) and impurity source location. HL-2A: Very strong screening against divertor source, but not for first wall source LHD: Modest screening against divertor source, but screening effective against first wall too
Magnetic field geometrical effect
InterpretationHL-2A: Strong up-downstream coupling
Preferable for increasing ratio at downstream, i.e. screening. No flow acceleration at upstream
weak against first wall source Inclusion of large upstream flow acceleration in experiments might alter the results
LHD: Enhanced transport in stochastic layer⊥ weaken up-down coupling modest screening effect compared to HL-2A can replace with reduction of thermal force ( )
Screening region is distributed poloidally screening effect independent of impurity source location
Validation of the model results in experiments is ongoing …….. 16
Edge impurity transport has been analyzed in LHD and HL-2A based on fluid impurity transport model using 3D edge transport code EMC3-EIRENE.
iD
iV qq //// /
iDq//
iDq
iDq//